Determination of optimal core fissile loadings in the TREAT Upgrade reactor

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5912587

Bhattacharyya, S K; Lell, R M; Ulrich, A J; Yang, S

The TREAT Upgrade (TU) reactor design is presently nearing completion. The reactor will be used to test LMFBR fuel under simulated accident conditions. The physics of the TU core is complicated by a number of factors related to the planned application of the facility. In this paper the design approach used to produce the core fissile loading spatial distribution needed to satisfy the requirement to test a number of different test clusters in various test loops in a transient operating mode is described. The TU core consists of a driver comprised of the pre Upgrade Zircaloy-clad TREAT fuel assemblies and a central converter region of new Inconel-clad fuel assemblies surrounding the test loop location. Separating the two concentric zones is a buffer zone that is made up of new Inconel clad assemblies operating at lower temperatures than the converter region.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5912587
• Report Number(s): CONF-831047-18; ON: DE83014710
• Resource Relation: Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TREAT REACTOR
REACTOR CORES
REACTOR KINETICS
CHEMICAL COMPOSITION
FUEL ASSEMBLIES
FUEL MANAGEMENT
OPTIMIZATION
AIR COOLED REACTORS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
KINETICS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors